ML19347D710
| ML19347D710 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo, 07000267 |
| Issue date: | 08/14/1980 |
| From: | Orlosky P, Pierro M NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| To: | |
| Shared Package | |
| ML19347D707 | List: |
| References | |
| 17892, PROC-800814, NUDOCS 8103261139 | |
| Download: ML19347D710 (31) | |
Text
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--y ACCCUNTABILITY &\\NUAL for Nuclear Science and Technology Facility State University of New York at Buffalo RIS
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SCOPE The Nuclear Science and Technology Facility (NSTF) Accountability Manual is based upon the requirements of Code of Federal Regulations Title 10 (10 CFR), Parts 30, 70, and 150.
(In particular, sections 30.55, 70.51, 70.53, 70.54, 150.16, 150.17, and 150.18.)
1.1 Purnose The purpose of the NSTF accountability =anual is to establish pro-cedures to ensure compliance with applicable regulations regarding shipping, receiving, records and reports, physical inventory and quantity verification of Special Nuclear Material (SNM) and Source Material (SSM). The procedures presented herein are designed to detect and inhibit any diversion or attempted diversion of such materials. Physical security and Health Physics procedures are not included in this manual.
1.2 Content 1.2.1 Review and Update The requirements for review and provisions for update of the NSTF Accountability Manual are pr.esented.
1.2.2 Administrative Organization and Controls The administrative structure of NSTF personnel is presented. Specific areas of responsibility for material accountability are delineated, Administrative controls are presented to ensure that procedures, protocols, and purchase specifications involving nuclear materials are reviewed and modified as necessary to reflect compliance with the provisions of this manual.
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1.2.3 Types of Material
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The types and physical forms of SNM and SSM which are utilised at ESTF are described.
1.2.4 Iten Control Areas The Item Control Areas (ICA) flor the NSTF are de fined. Allowable and typical locations of the materials specified under " Types of Material" are presented.
1.2.5 Material Quality Assurance Specifications for the verification of mass and enrichment and limits of error for nuclear materials are presented.
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1.2.6 Shipoing and Receiving i
Procedures for material accountability in shipping and receiving are presented. Said procedures include provisions for the ensurance of compliance with requirements for the reporting of SNM transactions.
4 1.2.7 Storage and Internal Trans fer r
Require:nents for identification, storage, and internal transfer of nuclear materials are provided.
1 1.2.8 Production and Burnup Calculations 4
l The calculational models for uranium and plutonium production and 4
burnup are described. Specifications of the required frequency for these criculations are also presented.
1.2.9 Inventory Requirements and procedures for physical inventory are presented.
Determination and settlement of Book-Physical Inventory Difference (3PID) are addressed.
1.2.10 Records and Reports Requirements for tho documentation of material accountability l
activities. are provided. Requirements for the routine and non-routine reporting of material status are also provided.
1.2.11 Distribution of Manuals Guidelines for the distribution of mansais and manual updates and l
4 modifications are presented.
2.
REVIDI AND UPDATE In addition to.the requirements of section 3 of this manual, the NSTF I
Operating Conunittee' will conduct an internal audit of nuclear material control procedures and management controls, as specified in this i
manual, in January of each year.
Minor changes may be adopted by the Operating Consnittee. Major changes r
will not'be made without NRC approval.
Af ter adoption, changes will be implemented by the' Accountability Officer and other individuals ' delegated accountabilicy responsibilities, within the provisions of section 3 of this manual.
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Distribution of modifications or updates to this manual shall be made pursuant to the requirements of section 12 of this manual.
Modifications of regulatory requirements for accountability or reporting shall be brought to the attention of the Operating Com-mittee by the Accountability Officer. The Operating Co=sittee shall then adopt any modifications to this manual that may be required.
3.
AD4INISTRATIVE ORGANIZATION AND CONTROLS 3.1 Organi:ation The NSTF nuclear materials management control function reports to the NST? Director. The responsibility for this function is delegated by the Director to an Accountability Officer.
(See Exhibit 4.)
Individuals may be designated by the Accountability Officer to transfer frem or receive nuclear materials into the Ites Control areas as specified in section 5 of this manual. Such individuals shall be responsible for the maintenance of internal records reflecting such transfers. Designation of these individuals shall be made in writing. The Accountability Officer shall be responsible for the implementation of the provisions set forth in this manual, and for the ensurance of compliance with all applicable nuclear material accountability regulatory requirements.
All NSTF or SUNY/ Buffalo RPD employees with responsibility for the transfer, storage, or utilization of nuclear materials shall comply with the directives of the Accountability Officer.
3.2 Controls All Operating Procedures, purchasing specifications, Radiation Pro-tection procedures, and experimental protocols involving nuclear The materials, shall be reviewed by the Accountability Officer.
Accountability Of ficer shall assure that nuclear material control
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~ procedures are, adequately reflected in such procedures and specifications. All transactions involving the receipt or shipment
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of nuclear materials shall be brought to the attention of the Accountability Of ficer by the individual (s) initiating the transaction.
Such notifications shall be made in writing.
4.
TYPES OF MATERIAL
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The following types of nuclear materials are utilized at NSTFs (a) One Fission Plate - ~ One Kilogram of 90 per cent enriched Uranium.
Powders and pellets.
(b) Miscellaneous UO2 (c) Nuclear instre=entation devices such as fission chambers and threshold detectors.
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4-(d) Natural Uranium suberitical reactor fuel slugs.
(e) Plutonium-Beryllium neutron sources (5 one curie, and 1 ten curie).
(f) Scrap critical reactor fuel (Broken, distorted, or spent pellets and elements.)
(g) New or cold reactor fuel elements and assemblies.
(h) In use or pool storage reactor fuel assemblies.
5.
ITO! CONTROL ARF.AS Material accountability at NSTF is accomplished on an item control basis. Five item control areas are herein defined.
ICA-1C control deck fuel storage vault.
ICA-1G gamma deck fuel storage vault.
ICA-2 reactor core and pool, storage facilities.
ICA-3 suberitical reactor tank.
ICA-4 balance of Facility, including Hot Cell and campus at large.
5.1 ICA-ic and ICA-1C Materials typically stored in ICA's 1C and 1G include cold fuel elements, fuel test assemblies, and miscellaneous materials such as uranium %ide powderpand pellets of varying enrichments. All fuel elements are mreu in specially fabricated racks to avoid the inadvertent mixing of elements.
5.2 ICA-2 ICA-2 includes the reactor core, the fuel element storage racks, neutron detector mounts, and the gamma irradiation facility. Material may, on occasion, be stored or utilized in the reactor tank in other temporary configurations. The entire reactor tank shall therefore be considered ICA-2.
The ICA-2 inventory shall be limited to fuel assemblies and Eements, fuct test assemblics and elements, nuclear instrumentation, or Plutonium-Beryllium sources. Material being irradiated inside the
- pneumatic conveyer system (PNC) shall be considered to be inside ICA-4.
S3 ICA-3 The inventory of the subcritical assmbly tank shall be limited to natural uranium fuel slugs and, wher.1.n use or temporary storage, the Plutonium-Beryllium sources.
- - Use of one curie Pu-Be sources in appropriate campus locations is allowed.
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5-5.4 ICA-4 The balance of the Facility, including the reactor irradiation facilities and Hot Cell, shall be designated ICA-4. Materials typically present in ICA-4 include a fission plate, Plutonium-Beryllium sources, and miscellaneous materials for use in experimental or test programs. As per specific license provisions, fuel elements or assemblies may be stored and/or manipulated inside the Hot Cell, pursuant to certain conditions.
When not in use, the fission plate is stored in a locked shielding cask on the neutron deck. The Pu-Be sources are nor= ally stored in locked shielding drums inside the contain=ent vessel. Exceptions to the normal storage locations are allowed when periodic utili:ation of the Pu-3e sources makes transfer to and frem, or storage within such locations impracticable. Pu-Be sources (one curie) =ay be loaned to other University depart =ents for use on ca= pus, with the approval of the Accountability Officer and the Ca= pus Radiation Safety Officer.
5.5 ICA Responsibility As specified in section 3.1 of this plaa, the Accountability Officer may delegate responsibility for operations involving nuclear material within an ICA to a qualified individual. Alternates may also be designated.
6.
OUALITY ASSURANCE 6.1 Reactor Fuel Elements The veador's values on mass and isotopic enrichment and limits of error (if provided) are accepted. Verification of mass and enrichment will be performed af ter receipt of the elements. Elements will be sampled on a random basis. Verification wil1~ consist of enrichments, using gamma ray scans. Cross element weight will be verified by weighing. gg pg pq gc.m pg
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The vendor's values on mass enrichment and limits of error are accepted for materials such as isotopic neutron sources, clad-natural uranium sluss, etc. Piece count verification shall be performed.
6.3 Other Materials Mass,' enrichment, and limits of error values supplied by the vendor are accepted, subject to verification. Minimum measurements for verification include gross weight, piece count and enrichment (by gamma-ray spectroscopy or other appropriate method. )
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.6.4 Exemotions Measurements are not required on materials which, based on the vendor's values, contain less than ten (10) grams each of U-235, U-233, and/or Pu.
7.0 SilIpPING AND RECEIVING 7.1 Receiving 7.1.1 Orders for nuclear materir,1 will be reviewed by the Accountability Of ficer for ceepliance with license conditions pri'or to release to the Purchasing Department.
7.1.2 Upon receipt, the ! M or SSM will be placed in an appropriate ICA.
A " Nuclear Materials Shipping / Receiving Report" (Exhibit 13 Form :M-1.)
shall be prepared and forwarded to the Accountability Officer.
7.1.3 Upon receipt from the shipper, the material quantities listed on the form NRC/ERDA-741 ' Materials Transaction Report (Exhibit 10) shall be verified as indicated in section 6 of this plan. The form NRC/ERDA-741 shall be completed and copies distributed in accordance with NRC printed instructions and 10 CFR 70.54, 7.1.4 Copies of the forms NRC/ERDA-741 and N31 shall be placed in the appropriate file and shall be available for inspection. Entries will be made in the Master and appropriate subsidiary accountability logs.
7.2 shioping 7.2.1 Prior to shipment, a foen NRC/ERDA-741 shall be filled out in accordance with printed instructions fran the NRC and 10 CFR 70.54.
A form NH-1 shall also be prepared.
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7.2.2 Upon shipment, form NRC/r.RDA-741 will be distributed as required.
Entrics will be made in the Master and appropriate subsidiary accountability logs.
7'. 2. 3 Copies of the forms NRC/ERDA-741 and NHL will be placed in the appropriate file, and shall be available for inspection.
7.3.
Discrepancies All shipper-receiver differences shall be reviewed by the Accountability Officer. It shall be the responsibility of the Accountability Officer N tifications to the NRC shall be made, to resolve such differences.
o subject to the requirements of 10 CFR 70 and 150.
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7.4 Responsibilities All activities described in this section shall be performed by the Accountability Officer or a written designee.
8.
TORACE AND INTERNAL TRANSFERS 8.1 Identification An Item ' Control Number (ICN) shall be ascribed to all items containing SNM or SSM. These numbers will facilitate rapid and accurate identification of nuclear materials. Tagging of corresponding items shall be performed if possible 8.2 Storage Storage of nuclear materials shall be in appropriate ICA's, subject to the Ibnitations of licenses R-77 and Stat-273.
8.3 Internal Transfers
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All transfers of nuclear material (except as specified in section 8.4) shall be docemented on a fors NM-2, " Internal Transfer Report". Copies of said forms will be distributed to all individuals responsible for the ICA's involved, the Accountability Officer, and the appropriate file. Entries shall be made fr. the master and subsidiary accountability logs involved.
If material is consumed, appropriate entries shall also be made.
8.4 Exemptions The trans fer of Pu-Be sources need not be documented on forms NM-2.
A status display board shall be used to indicate the disposition of such sources. This board shall be kept accurate at all times.
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9.
. PRODUCTION AND BURNUP CALCULATIONS Uranium burnup and plutonium production and burnup will be calculated at least semi-annually, on the basis of reactor operating history.
Appropriate entries will be made in the master and subsidiary accounta-bility logs. The results of these calculations will be. reported using the most up-to-date Material Status Reports.
(See section 11.)
Reports shall be filed by April 30 and October 30. Two methods may be used to perform these calculations. The primary method shall be utilization of computer codes as described in Exhibit 12. If the computer calculations cannot be performed, calculations shall be per-formed by hand, as described in Exhibit 12.
These calculations shall be performed by the Accountability Officer and/or his designee.
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INVENTORY 10.1 Frequency
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A physical inventory of all Nuclear Material will be conducted in January of each year.
LO.2 Preoaration Prior to each physical inventory, the Accountability Officer shall update the previous " Physical Inventory Record" (F,orm NM-3), Exhibit based on Material Transaction Reports (NRC/ERDA-741) and Internal Material Transfer Reports (M4-2) for the inventory period, and the Accountability Logs. The updated Physical Inventory Record shall be used as a source document for the physical inventory.
10.3 Procedure The physical inventory of special nuclear material shall consist of a piece count and identification of all items within each item control area. The identification of fuel assemblies which have not been involved in inter-ICA transfers during the inventory period will be based on the current reactor loading record. Inventory of the Suberitical Reactor (ICA-3) fuel slugs will be by piece count only.
(SSM)
_10.4 Book-Physical Inventory Differences (BPID 's)
The Accountability Of ficer shall recencile the Book and Physical Inventories. Any BPID shall be investigated by the Accountability Officer and proper adjustments will be made.
11.
RECORDS AND REPORTS 11.1 Accountability Logs S x Accountability Logs shall be maintained. A master log shall be maintained by.the Accountability Officer. In addition, a subsidiary log book shall be ' maintained for each ICA. Subsidiary logs shall be e
maintained by the Accountability Officer or his ' designee. '
e The logs for ICA's IG and IC shall be kept in the respective ICA's, The logs for ICA's 2, 3, and 4 shall be kept in the control room e
archives. The master log shall be filed by the ~ Accountability Officer.
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11.2 Central Files The Accountability Of ficer shall maintain in a centralized location, files for the following documents:
11.2.1 Master Accountability 1.og.
11.2.2 Material Status Reports (NRC/ERDA-742).
11.2.3 Material Transaction Forms (NRC/ERDA-741).
11.2.4 Forms NM1.
11.2.5 Forms }M2.
11.2.6 Forms !M3..
11.2.7 Burnup and production calculations.
11.2.8 Written designations of accountability responsibilities.
11.2.9 Copies of instructions for the completion of Forms NRC/ERDA-741 and 742.
11.2.10 Two copies cf this manual and copies of updates or modifications.
11.2.11 Copies of reports summarizing Nuclear Material Quality Assurance measurements.
11.2.12 Copies of applicable portions of 10 CFR. '70 11.2.13 Records of Assignment of ICN's.
11.2.14 Reports of any BPID's or violations of this manual.
11.2.15 Reports of audits, as specified in section 2.
11.2.16 Correspondence regarding items 1-15.
11.2.17 Blank forms NM1, NH2, NM3, 741, and 742.
11.3 Reports Forms NRC/ERDA 741 and 742. shall be filed, as specified in 10 CFR.7'.N
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Reports of the actual or possible loss or theft of nuclear materials shall be made to the NRC as specified in 10 CFR. Any unresolvable BPID's shall be promptly reported to the NRC.
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.. 12.
DISTRIBUTION OF MANUALS Copies of the Accountability Manual shall be distributed as follows:
1.
NSTF Director.
2.
Operations Manager
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RPD Manager.
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Reactor Engineer.
5.
All Senior Reactor Operators.
6.
Two copies to File.
7.
Control Room Archives.
4 8.
Accountability Of ficer.
Changes,or updates to the Accountability Manual shall be incorporated into all distributed copies by the Accountability Of ficer or his designee.
APPROVED BY OPERATING COMMITTEE Administration M,. -
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EXIIIBIT 1 Receipts Flowsheet Order Approval
'r Order Placed v
Material Received RPD Forms
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(Notification of NSTF of Date Generated to be received prior to re-ceipt only in case of large shipe.ents)
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v Transfer to Aporocriate Storage Location v
Quantity Shioner Originated 741 Verification si se NSTF Accountability -
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ORGANIZATION ClLWT SHOWING ACCotRITABILITY FUNCTION j
PRESIDENT State University of NY at Buffalo i
VICE PRESIDENT for Academic Af fairs DIRECTOR Nuclear Science and.
Technology Facility Radiation Safety officer g
5 5a Radiation Protection Accountability Reactor Operations Manager
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Manager and Staf f officer Engineer and Staff Staff t
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EXIIIBIT 9 FORM NRC/ERDA.742 If h NUCl LAH HLteln AIOHY COMMtSSION (7 77)
- AND APPROVEO BY GAO 13 CF R 7C/t R O AM 7401 U S. ENEHGY RESEARCH AND DEVELOPMENT ADMINISTHATION 8 180225 (R0041) an io...oinoa. u. onw.i.i
' ' ' ' #8 M ATERI AL STATUS REPORT
- 1. NAME AND ADDRESS
- 2. LICENSE NUMBER (S) 3 REN T W4G sCgm agm p, SYMBOL. (RIS)
- 4. REPORT PERICO
- 5. MATE RI AL TYPE (Submot separate report for pynn
,n each type)
MATERI AL ACCOUNTABILITY S.
CUANTITY 8Y ELEMENT AND ISOTOPE WEIGHT A.
E LEMENT WEICHT B.
ISOTOPE WEIGHT i
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UE GI NNIN(i IN VEN TOitY LHDA CWNED l
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ULGl.'.NING INVLtJ f 0HY NOI LHIJA OWNLD RECEIPTS
- 13. PRCCUREMENT - OTHER
- 14. D00 RETURNS - USE A
- 15. 000 RETURNS - USE 3
- 16. COO RETURNS - OTHER USES
- 21. PRODUCTION
- 22. FRC'.1 OT;4ER MA TEf tt ALS
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- 40. TOTAL YV' I
REMOVALS 41.- EXFENDED IN SPACE PROGRAMS l
- 42. SALES TO ERDA HlS TO:
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- 46. OOO - O THE R USES
- 47. EXPENDEO IN ERDA TESTS 48..OUTINE TESTS
,49.. SHIPPER. RECEIVER Of FFERENCE
'. 51. SHIP'.'E NTS RE PORTED TO N RCiE RDA ON MR*1 N HC/ER DA.741 (Not hstrd e/se-TO:
nnere) Ros it. OEGR ADATION TO OTHER MATERIALS
- 11. l>C t.A f
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Ft'.:;iGN AND TitANSMU TATION
- 74. HOR *.8AL OPERATIONAL 1.OSSES/ME ASURED OtSCAHOS
- 75. ACC:CENTAL LOSSES
- 77. INVENTORY DIFFERENC3
- 30. ENC 1'4C INVENTCRY - ERDA CWNED
- 81. ENCt'+G IN JEN TORY - NOT EROA CWNED
- 82. TOTAL
EXIIIBIT 9a COMPOSITION OF ENDING INVENTORY
- 2. REPOR TING til tDEN TIFICATION
SYMBOL.
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- ~~1 NON.ERDA OWNED INVEN FORY 3A MATERIAL TYPE 3.8. E NRICHMENT LEVE L (for U 235) tes sss ses 810 4 t NV L t. fish Y COMPO*;t tiotd OESCRIPTION ELEMEN T WElGH T ISO TCPE WEIGH T r,OG E 815 21)
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- ec in #4Et'OVE f tY PRr.CCZES 344
- Altl't AL NOT IN PHCOESS
~y jl (f3 l' UrilHi<.4CI ATED 3CR AP AWA4 TING RECOVERY uco l UtelH MAG % fiO 3CHAs' AWAIT?NG OBSPOSAL TUTAL
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3 g.3 Hot ERCA O.vneet.' on trent snte of form 1J2: for U.235 l
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5.
ERDA OWNED INVENTORY
[
(Refer to ERDA Afanual Avoendia 7401C for rencrting instructions) 1 1
- E 30"I EHDA UESA (J S A I I, g!! /EN TQi4 Y
- 'AIC 3,OiC*E PROO'JC I PI At.
Lis'.1P'*de PRC.ECT 3 CRAP CATE.
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NU*MBER PHOC GORY T!ON I E
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"Endons inventory - EROA Owne't.** on front sede at form 142.)
To the best of tny knowlettge and belief the infrumation given at;ove, and in any attacted schedules, is true, comolete and correct.
DATE SIGf4 A TL R E TITLE 18 U S.C. SECTION 1001: ACT OF JUNE 25.1948; 62 STAT. M9; MAKES IT A CRIMIN AL OFFENSE
.n o n.s.,
TO MAKE A WILLFULt.Y FALSE STATEMENTOR REPRESENTATION TO ANY DEPARTMENT OR AGENCY OF THE UNITED STATES AS TO ANY MATTER WITHIN ITS JURISOICTION.
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EXHIBIT 11 NSTF Accountability Log Individual sections of the log are used for each license and each type of material (enriched uranium and plutonium). The formats used in the logs are as follows:
Page Heading, ' License Number, and Material Type Column.1 Date Received Column 2 Date Shipped Column 3 From: Shipper Identification, Name and/or RIS Column 4 To: Receiver Identification, Name and/or.RIS, and Trcnsfer Series Number
- Column 5 Item Description Column. 6 Element: Weight in grams Column 7
' Isotope: Weight in grams Column 8 Per cent Enrichment s.
Column-9 Location' Column ~10 Balance Element: Running Inventory Column"11 Balance Isotope:- Running Inventory Column 12 Remarks
~
e E
'5-A e
Ng-p wee m**
Wh +
-,s f
3 mw
~v mi---
7 9
EXHIBIT 12 DESCRIPTION OF REACTOR FUEL BURNUP CALCUIATIONS A.
Computer Analysis The following data are used to calculate fuel burnup at NSTF:
1.
Initial composition of fuel.
2.
Composition of fuel at end of the last preceding report period.
3.
Fuel exposure history during report period.
4.
Iteasured power distribution of exposed fuel.
5.
A table of isotopic number densities vs. exposure in $~D/ Tonne.
1
The number density table was developed using reactor analysis codes BMt ,
3 4
2 5
F0Di, FOG, KINDLE, and DANCOFF. These calculations need only be made once, assuming that fuel enrichment's and/or element / assembly geometries remain the'same.
If such changes are made in the future (not anticipated),
a new table will be generated.
At the end of each reporting period, the data specified in items 2, 3, and 4 are collected and input into a program (BURNUP.)
The output of this program is the isotopic compositions of all fuel assemblies in use. The calculation is made for each fuel loading configuration used during the reporting period.
(See Figure 1.)
B.. Hand Calculations-
~
~
It is possible that the 'SUNY/ Buffalo computer may not be available for burnup calculations. In this situation, the calculations may be made-by hand,
- using th'e identical algorithm contained in program BURNUP.
A description of titis algorithm is provided by Figure 2.
~
4 O%
e-J.. -. -
. t..
i e
e Figure 1.
COEI Exposure History V
s/ s/ _ _
Progra BURNUP Measured Power Distribution Burnup arl Isotopic
/
Inventory of Fuel in Use f '
~
i b
g
- contains # density table.
n
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Figure 2 Cide Algorithms For assembly (J)
Obtain X(J) = previous burnup in MtJD: available from Tonne listing.
Power distribution factor FF(J)
=
initial gss U-235
- A25 (J)
=
initial gas U-238 A28(J)
=
last ETS}*
Set Y(J)
(MRH)" #"!
F
=
- assemblies 24 hrs
/11,33.7 sum 1 in core day
- assemblies where sum 1
= E XASS (J)
FF J=1 XASS (J)
,, = Mass of UO2 (initial) in assembly in Kg.
B(J) --
X(J) + Y(J) = Total Burnup on element J 7
~
convert B(J) to MWD / Tonne UO 2
B(J) - B(J)/1.1337 Interpolate in Kindle data to obtain ENI25, CII28, ENI26, ENI39, ENI49, ENI40, ENI41, ENI42.
calculate: gms 235 = AMI25
= ENI25/(.5566E-03)
- A25 mas 238 = AMI28
=-ENI28/.86090E-02) x A28 Irradiation Products AMI26 = gas 236 236 57
= (ENI26/ENI25)
- AMI25 '
- 35. 4
,AMI28 238.0508 / ENI28 AMI39 ' = gas NP239
= ENI39. 239 AAA AMI49 = gas PU239 = ENI49 239.0522 AAA
-AMI40 = gms PU240 - ENI40 240.054 AAA ~
~
AMI41 = gms PU241' = ENI41 241. AAA AMI42 = gns PU242 = ENI42 242.059 AAA
a e
' REFERENCES
~
1.
R. ' A. Blaine, "BAM IV, EXTENSION AND CONVERSION 0F 'EHE BMt CODE TO FORTRAN IV",' AI-64-MDiO-261, Dec., 1964.
2.'
R. A. Blaine, "THREDES: ATOiICS INTERNATIONAL THERMAL REACTOR DESIGN SYSTDI" AI-CE-MEMO-11.
3.
D. J. McGoff, " FORM - A FOURIER TRANSFORM FAST SPECTRQi CODE FOR THE i
IBM-709" NAA-SR-Mm0-5766, Sept., 1960.
- 4. -
H.. P. Flatt, "THE FOG ONE-DDiENSIONAL NEUTRON DIFFUSION EQUATION CODES", NAA-SR-6104, Jan., 1961.
j 5.
I. Carivik, "THE DANCOFF CORRECTION IN SQUARE AND HEXAGONAL LATTICES",
Nuc. Sci. - and Eng. 29 (3), pp. 325-335, Sep t., 67.
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EXHIBIT 13 NSTF Internal Forms 9
a I
se GP N
4 O
O
FOlet NM-1 e
NSTF Nuclear Materials Shipping / Receiving Report RIS:ZYL.- -
Material: I l
Shipped Date l
l Received Date License Number:
l l R-77
-l l SNM-273 Item Control Area :
Material Location:
Transfer Series Number:
Material Description (include container description if appropriate):
Quantity Verification Method:
Data:
' ~ ~ ~ ~ ~
-Radiation Protection Data Container Surveys:
Container Smears:
Accountability RPD Assigned Item Control Number by:
on:
^
~ ~ ~ -.
YORM Ri-2 NSTF Internal Nuclear Material Transfer Report From:
To:
Date:
Fabricated Items Material Description (include Identification Code):
Item Control Number (s)
Material Quantities and Earichments:
Non-Fabricated Items Material
Description:
. ~
Item Control Numbers Material Use (if material to be consumed, indicate):
Quantity and Enrichment of Materials Transferred:
Material Balance 4
l l
l Transferred By Received By e
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(
NSTF Physical Inventorv Record Page of Date:
Item Control Area:
Inventoried by:
Item Material License Reported Control Descrip tion Number on 742 Number
.